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Journal Articles

Tritium release behavior from the graphite tiles used at the dome unit of the W-shaped divertor region in JT-60U

Katayama, Kazunari*; Takeishi, Toshiharu*; Manabe, Yusuke*; Nagase, Hiroyasu*; Nishikawa, Masabumi*; Miya, Naoyuki

Journal of Nuclear Materials, 340(1), p.83 - 92, 2005/04

 Times Cited Count:8 Percentile:49.02(Materials Science, Multidisciplinary)

no abstracts in English

JAEA Reports

Achievements of element technology development for breeding blanket

Department of Fusion Engineering Research; Department of Materials Science

JAERI-Review 2005-012, 143 Pages, 2005/03

JAERI-Review-2005-012.pdf:11.74MB

no abstracts in English

Journal Articles

Fusion materials and hydrogen

Nagasaki, Takanori*; Yamaguchi, Kenji; Konishi, Satoshi*

Nihon Genshiryoku Gakkai-Shi, 46(11), p.770 - 779, 2004/11

no abstracts in English

Journal Articles

Extraction of hydrogen from water vapor by hydrogen pump using ceramic proton conductor

Kawamura, Yoshinori; Konishi, Satoshi; Nishi, Masataka

Fusion Science and Technology, 45(1), p.33 - 40, 2004/01

 Times Cited Count:25 Percentile:81.9(Nuclear Science & Technology)

Aiming at realization of the efficient blanket tritium recovery system of a fusion reactor, research and development of the hydrogen pump using the proton conductor are furthered. One of the advantages of the system using the hydrogen pump is concurrent processing of hydrogen isotopes and water vapor by one component. In this work, experimental research on the hydrogen extraction characteristic in a water molecule was performed with the hydrogen pump using SrCe$$_{0.95}$$Yb$$_{0.05}$$O$$_{3-alpha}$$. In hydrogen extraction from a water molecule, application of the threshold, voltage corresponding to the decomposition energy of water, is necessary. The observed threshold was about 500-600mV at 873K and decreased with the increase in water vapor pressure. About pumping of H$$_{2}$$-H$$_{2}$$O mixture gas, the permeation of H$$_{2}$$ anteceded water decomposition, and the threshold of water decomposition increased with the increase in hydrogen partial pressure. In order to process concurrently, application of fairly higher voltage is expected to be necessary.

Journal Articles

Transport properties of hydrogen isotope gas mixture through ceramic protonic conductor

Kawamura, Yoshinori; Konishi, Satoshi; Nishi, Masataka; Kakuta, Toshiya*

Fusion Science and Technology, 41(3), p.1035 - 1039, 2002/05

To establish the nuclear fusion reactor, tritium bred in the breeder blanket of the fusion reactor must be recovered effectively. The present authors have proposed the blanket tritium recovery system using the hydrogen pump with solid electrolyte membrane. Hydrogen isotopes including tritium can be separated from helium purge gas of the breeder blanket by the protonic conductor membrane which pumps out hydrogen isotopes selectively by applying a few potential difference between its faces. Perovskite-type ceramic such as SrCe$$_{0.95}$$Yb$$_{0.05}$$O$$_{3-a}$$, is one of the candidate protonic conductor for hydrogen pump and its ionic hydrogen transportation properties have been investigated. Deuterium transportation properties have also been investigated to understand the isotope effect. Through the investigation up to now, the basic hydrogen isotope transportation property of SrCe$$_{0.95}$$Yb$$_{0.05}$$O$$_{3-a}$$, its technical feasibility, and issues for further development toward the practical devices were revealed.

Journal Articles

${it In-situ}$ tritium recovery experiments of blanket in-pile mockup with Li$$_{2}$$TiO$$_{3}$$ pebble bed in Japan

Tsuchiya, Kunihiko; Nakamichi, Masaru; Nagao, Yoshiharu; Enoeda, Mikio; Osaki, Toshio*; Tanaka, Satoru*; Kawamura, Hiroshi

Journal of Nuclear Science and Technology, 38(11), p.996 - 1003, 2001/11

 Times Cited Count:23 Percentile:82.31(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Electrochemical properties of hydrogen concentration cell with ceramic protonic conductor

Kakuta, Toshiya*; Konishi, Satoshi; Kawamura, Yoshinori; Nishi, Masataka; Suzuki, T.*

Fusion Technology, 39(2-Part2), p.1083 - 1087, 2001/03

no abstracts in English

Journal Articles

Adsorption isotherms of tritium on various adsorbents at liquid nitrogen temperature

Kawamura, Yoshinori; Enoeda, Mikio; Willms, R. S.*; Zielinski, P. M.*; Wilhelm, R. H.*; Nishi, Masataka

Fusion Technology, 37(1), p.54 - 61, 2000/01

no abstracts in English

Journal Articles

Characterization of self-powered neutron detector at high temperature under neutron irradiation

Nakamichi, Masaru; *; Kawamura, Hiroshi; Sagawa, Hisashi; Nakazawa, Masaharu*

Fusion Technology 1996, 0, p.1591 - 1594, 1997/00

no abstracts in English

Journal Articles

A Tritium recovery system from waste water of fusion reactor using CECE and cryogenic-wall thermal diffusion column

Arita, Tadaaki; Yamanishi, Toshihiko; Iwai, Yasunori; Okuno, Kenji; Kobayashi, Noboru*; Yamamoto, Ichiro*

Fusion Technology, 30(3), p.864 - 868, 1996/12

no abstracts in English

Journal Articles

Recovery of hydrogen isotopes and impurity mixture by cryogenic molecular sieve bed for GDC gas cleanup

Enoeda, Mikio; Kawamura, Yoshinori; Okuno, Kenji; Tanaka, Kenichi*; Uetake, Mitsuru*; Nishikawa, Masabumi*

Fusion Technology, 28(3), p.591 - 596, 1995/10

no abstracts in English

JAEA Reports

TSTA/FCU-JFCU tritium experiment on breeding blanket interface under the collaboration of JAERI-US/DOE (extended Annex IV); March 1993

Enoeda, Mikio; Yamanishi, Toshihiko; Yamada, Masayuki; Konishi, Satoshi; Okuno, Kenji; Willms, R. S.*; Taylor, D.*; W.Harbin*; Bartlit, J. R.*; Anderson, J. L.*

JAERI-Research 95-034, 29 Pages, 1995/05

JAERI-Research-95-034.pdf:0.99MB

no abstracts in English

Journal Articles

In situ tritium recovery from Li$$_{2}$$O irradiated in a fast neutron flux; BEATRIX-II, Phase II temperature-change canister

Slagle, O. D.*; Kurasawa, Toshimasa; Takahashi, Tadashi; Hollenberg, G. W.*; Verrall, R. A.*

Journal of Nuclear Materials, 219, p.265 - 273, 1995/03

 Times Cited Count:4 Percentile:43.23(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Recovery of tritium by cryogenic molecular sieve bed in breeding blanket interface condition

Enoeda, Mikio; Kawamura, Yoshinori; Okuno, Kenji; Nishikawa, Masabumi*; Tanaka, Kenichi*

Fusion Technology, 26(3), p.664 - 667, 1994/11

no abstracts in English

JAEA Reports

Japanese contributions to ITER testing program of solid breeder blankets for DEMO

Kuroda, Toshimasa*; Yoshida, Hiroshi; Takatsu, Hideyuki; *; Mori, Seiji*; *; *; Hirata, Shingo*; Miura, H.*

JAERI-M 91-063, 72 Pages, 1991/04

JAERI-M-91-063.pdf:1.55MB

no abstracts in English

JAEA Reports

Technical Evaluation of Major Candidate Blanket Systems for Fusion Power Reactor

Tone, Tatsuzo; Seki, Masahiro; Minato, Akio; ; *; *; *; *; ; *; et al.

JAERI-M 87-017, 737 Pages, 1987/03

JAERI-M-87-017.pdf:16.73MB

no abstracts in English

Journal Articles

Tritium recovery experiments in JRR-2/VOM

Watanabe, H.; Kurasawa, Toshimasa; Roth, E.*; Vollath, D.*

Proc.Int.Symp.on Fusion Reactor Blanket and Fuel Cycle Technology, p.33 - 36, 1987/00

no abstracts in English

JAEA Reports

JAEA Reports

JAEA Reports

Brief Review on Tritium Recovery from Inert Gases by Uranium Getter Beds

; ; ;

JAERI-M 85-174, 28 Pages, 1985/11

JAERI-M-85-174.pdf:0.53MB

no abstracts in English

26 (Records 1-20 displayed on this page)